Patent Assignment
Reel/Frame 066373/0604
Security Interest
Recorded: 2024-01-26
Pages: 60
Assignors
WESTINGHOUSE ELECTRIC COMPANY LLC
Executed: 2024-01-25
BHI ENERGY I SPECIALTY SERVICES LLC
Executed: 2024-01-25
STONE & WEBSTER, L.L.C. (FORMERLY STONE & WEBSTER, INC.)
Executed: 2024-01-25
Assignee
DEUTSCHE BANK AG NEW YORK BRANCH, AS COLLATERAL AGENT
1 COLUMBUS CIRCLE, NEW YORK, NEW YORK, 10019
Covered Properties
(606)
Annular Nuclear Fuel Rod
PCT:
PCT/US2022/078480 ↗
Producing Ac-225 Using Gamma Radiation
PCT:
PCT/US2022/079372 ↗
Bottom Nozzle with Protective Insert
PCT:
PCT/US2022/079450 ↗
Non-Invasive Liquid Metal Flow Measurement in Liquid Metal Fuel Assemblies, Reactor Coolant Pumps, and Test Cartridges
PCT:
PCT/US2022/079804 ↗
A Device and Method for Rapidly Measuring the Activity of Nuclear Isotopes Contained Within a Cylindrical Enclosure Using the Current Output from a Lead Self-Powered Detector Element
PCT:
PCT/US2023/019389 ↗
Fuel Cladding Covered by a Mesh
PCT:
PCT/US2023/021694 ↗
Nuclear Flux Thimble Irradiation Target Insertion and Retrieval Mechanism
PCT:
PCT/US2023/031659 ↗
Nuclear Power Source, Nuclear Battery Assembly, and a Method of Manufacture Thereof
PCT:
PCT/US2023/031678 ↗
Method and Device for Direct Production of Radio-Isotope Based Cancer Treatment Pharmaceuticals
PCT:
PCT/US2023/062015 ↗
Flow Conditioning Device for Steam Generator
PCT:
PCT/US2023/064375 ↗
Use of Sub-Critical Neutron Multiplication Driven by Electronic Neutron Generators to Produce Radioisotopes
PCT:
PCT/US2023/068510 ↗
Wireless Power Level and Power Distribution Monitoring and Control System for Subcritical Spent Fuel Assembly Array Using Removable Sic Neutron Detector Thimble Tube
PCT:
PCT/US2023/070401 ↗
Devices, Systems, and Methods for Enhancing the Implementation of Control Circuits for Nuclear Instrumentation and Control Systems
PCT:
PCT/US2023/070414 ↗
Method for Performing Star/Arwv Reconciliation
PCT:
PCT/US2023/073859 ↗
Fiber Reinforced Multi-Layered Wear and Corrosion Coatings of Zirconium Alloy Nuclear Fuel Cladding
PCT:
PCT/US2023/074435 ↗
Method to Reduce Nuclear Radiation Induced Speckling in Video Images
PCT:
PCT/US2023/075216 ↗
Devices, Systems, and Methods for the Enhanced Operation of Hydraulic Control Units of a Control Rod Drive Mechanism to Regulate Nuclear Flux in a Reactor Core
PCT:
PCT/US2023/076569 ↗
Manufacture of Heat Pipe Wicks Utilizing in-Situ Rolling and Hydroforming Device
PCT:
PCT/US2023/077394 ↗
Production of Radioisotopes with Highly Enriched Target Enclosure Material
PCT:
PCT/US2023/077638 ↗
Heat Pipe Wick Bonding Through Crimping
PCT:
PCT/US2023/077645 ↗
Additively Manufactured Cobalt Burnable Absorber Capsules
PCT:
PCT/US2023/077696 ↗
Use of Oxidation Resistant Coatings to Increase Thin Walled Cladding Tensile Strength to Increase Uranium Loadings
PCT:
PCT/US2023/078430 ↗
Solid-State Fluid Thermal Bonded Heat Pipe Micro-Reactor
PCT:
PCT/US2023/080027 ↗
Electromagnetically Deployable and Retractable Irradiation Capsule Holding Mechanism
PCT:
PCT/US2023/083331 ↗
Effective Coating Morphology to Protect Zr Alloy Cladding from Oxidation and Hydriding
PCT:
PCT/US2023/084991 ↗
Eddy Current Data Union
Health Monitoring Display System for a Complex Plant
Component Interface Module
Control System Display for Monitoring a Complex Process
Method of Operating a Nuclear Power Plant at Multiple Power Levels
Patent:
6,674,826 →
Application:
10/252,496 →
Facility Life Management Method
Patent:
8,571,911 →
Application:
10/298,157 →
Subcritical Reactivity Measurement Method
Seal Arrangement for in-Core Instrument Housing
Method of Closing a Pressure Vessel
Method of Establishing a Nuclear Reactor Core Fuel Assembly Loading Pattern
Reactor Pressure Vessel
Unirradiated Nuclear Fuel Component Transport System
Patent:
6,748,042 →
Application:
10/424,480 →
High Energy Absorption Top Nozzle for a Nuclear Fuel Assembly
Patent:
6,738,447 →
Application:
10/444,469 →
Crud-Resistant Nuclear Fuel Cladding
Patent:
6,813,329 →
Application:
10/459,777 →
Miniature Manipulator for Servicing the Interior of Nuclear Steam Generator Tubes
Pressurized Water Reactor Shutdown Method
Nondestructive Examination of High Pressure Turbine Cylinders
Patent:
6,886,407 →
Application:
10/646,136 →
Method for Calibrating Steam Generator Water Level Measurement
Nuclear Reactor Fuel Assemblies
Head Assembly
Bwr Inspection Manipulator
Method of Operating a Nuclear Power Plant at Multiple Power Levels
Nuclear Fuel Assembly Debris Filter Bottom Nozzle
Method of Inspecting a Heat Exchanger and Computer Program Product for Facilitating Same
Nonintrusive Method for the Detection of Concealed Special Nuclear Material
Jet Pump Assembly Repair Method
Method for Controlling Steam Generators
Patent:
6,886,502 →
Application:
10/874,666 →
Nuclear Fuel Assembly Protective Grid
Reactor Pressure Vessel
Method and Algorithm for Searching and Optimizing Nuclear Reactor Core Loading Patterns
An Eddy Current Method of Inspecting a Pressure Vessel Shell
Device and Method for Ultrasonic Inspection Using Profilometry Data
Helically Fluted Tubular Fuel Rod Support
Film Riding Shaft Seal
System and Method for Determining Fluctuating Pressure Loading on a Component in a Reactor Steam Dome
Spectroscopy-Based Safety System and Method for a Vacuum Arc Remelt Furnace
Gas Phase Electrolyzer Process for Producing Hydrogen
Advanced Gray Rod Control Assembly
Printed Circuit Card
Patent:
7,386,086 →
Application:
11/242,171 →
Over Temperature and Over Power Delta Temperature Operating Margin Recovery Method and Reactor System Employing the Same
Patent:
7,596,198 →
Application:
11/367,001 →
Shipping Package Up-Ender
Method for Analysis of Pellet-Cladding Interaction
Nuclear Fuel Assembly Control Rod Drive Thimble to Bottom Nozzle Connector
Solid State Reversing Ac Motor Starter with Dc Power Source
Current Limiting Dc Motor Starter Circuit
On-Line Testable Solid State Reversing Dc Motor Starter
Steam Generator Nondestructive Examination Method
Steam Generator Loose Parts Collector Weir
Tube-In-Tube Threaded Dashpot End Plug
Computerized Procedures System
Nuclear Fuel Assembly
Method of Assessing the Performance of a Steam Generator
Unirradiated Nuclear Fuel Component Transport System
Removal of Niobium Second Phase Particle Deposits from Pickled Zirconium-Niobium Alloys
Method of Applying a Burnable Poison Onto the Exterior of Nuclear Rod Cladding
Upper Internals Arrangement for a Pressurized Water Reactor
Nuclear Reactor Control Rod Spider Assembly
Nuclear Reactor Vessel Fuel Thermal Insulating Barrier
Nuclear Reactor Downcomer Flow Deflector
Hydrogen Generation Process with Dual Pressure Multi Stage Electrolysis
Nuclear Reactor Robust Gray Control Rod
Nuclear Reactor Internals Alignment Configuration
Nuclear Reactor Alignment Plate Configuration
Pipe Clamp
Permanent Seal Ring for a Nuclear Reactor Cavity
Patent:
7,813,464 →
Application:
11/952,358 →
Eddy Current Data Interpolation/Extrapolation
Method of Improving the Spent Nuclear Fuel Burnup Credit
Cartridge Type Vortex Suppression Device
Nuclear Reactor Fuel Assembly
Advanced Logic System
Patent:
7,870,299 →
Application:
12/026,703 →
Pressurized Water Reactor Flow Skirt Apparatus
Advanced Gray Rod Control Assembly
Patent:
8,537,962 →
Application:
12/028,119 →
Neutron Absorber Consisting of Refractory Metal Infused with Discrete Neutron Absorber
Removal of Niobium Second Phase Particle Deposits from Pickled Zirconium-Niobium Alloys
Steam Generator Dual System Sludge and Loose Parts Collector
Nuclear Fuel Assembly with a Lock-Support Spacer Grid
Reinforcement for a Nuclear Fuel Assembly
Nuclear Core Component Hold-Down Assembly
Fuel Rod Internal Pressure Measurement
Steam Generator Dual Head Sludge Lance and Process Lancing System
Enhanced Steam Dump (Bypass) Control System
Patent:
7,742,555 →
Application:
12/172,688 →
Reactor Dosimetry Applications Using a Parallel 3-D Radiation Transport Code
Removal of Niobium Second Phase Particle Deposits from Pickled Zirconium-Niobium Alloys
Hatch Mechanical Locking System
Neutron Shielding Panels for Reactor Pressure Vessels
Subcritical Reactivity Measurement Method
Tube-In-Tube Threaded Dashpot End Plug
Failure Detection and Mitigation in Logic Circuits
Nuclear Fuel Assembly with Pivot Dimpled Grids
Process for Adding an Organic Compound to Coolant Water in a Pressurized Water Reactor
Non-Destructive Pipe Scanner
Modular Plate and Shell Heat Exchanger
Pipe Scanner
Two Step Dry UO2 Production Process Utilizing a Positive Sealing Valve Means Between Steps
Nuclear Fuel Assembly Protective Bottom Grid
Dynamic Port for Measuring Reactor Coolant Pump Bearing Oil Level
Reactor Coolant Pump Motor Load-Bearing Assembly Configuration
Helically Fluted Tubular Fuel Rod Support
Domed Diaphragm / Insert Plate for a Pressure Vessel Access Closure
Control Rod Drive Outer Filter Removal Tool
Wireless Transmission of Nuclear Instrumentation Signals
An Eddy Current Inspection Probe for Inspecting the Interior of a Tubular Member
Nuclear Fuel Assembly Support Grid
Steam Generator Nondestructive Examination Method
Thermally Activated Shutdown Seals for Rotatable Shafts
Core Shroud Corner Joints
Electrical Connector Assembly, Test Lead Assembly Therefor, and Associated Method
Upper Internals Arrangement for a Pressurized Water Reactor
Inspection Mode Switching Circuit
Process for Application of Lubricant to Fuel Rod During Fuel Assembly Loading Process
Expansion Gap Radiation Shield
Protective Grid Attachment
Alkylated Aromatics Production
Method of Processing Steam Generator Tubes of Nuclear Power Plant
Method of Modeling Steam Generator and Processing Steam Generator Tube Data of Nuclear Power Plant
Enhanced Steam Dump (Bypass) Control System
Dual Drive Winch and Nuclear Reactor Vessel Maintenance Apparatus Employing Same
Under Vessel Local Power Range Monitor Exchange Tool
Digital Nuclear Control Rod Control System
Triuranium Disilicide Nuclear Fuel Composition for Use in Light Water Reactors
Reactor Head Seismic Support Tie Rod System
System and Method for Removal of Dissolved Gases in Makeup Water of a Water-Cooled Nuclear Reactor
System for Exchanging a Component of a Nuclear Reactor
Alternate Feedwater Injection System to Mitigate the Effects of Aircraft Impact on a Nuclear Power Plant
Nondestructive Inspection Method for a Heat Exchanger Employing Adaptive Noise Thresholding
Primary Neutron Source Multiplier Assembly
Calibration Detection System and Method
Method for Automated Position Verification
Nuclear Fuel Assembly Hold Down Spring
Unirradiated Nuclear Fuel Component Transport System
Advanced Logic System
Patent:
8,156,251 →
Application:
12/914,724 →
Advanced Logic System Diagnostics and Monitoring
Patent:
8,554,953 →
Application:
12/914,737 →
Wedge Positioning Apparatus for Jet Pump Assemblies in Nuclear Reactors
Miniature Sludge Lance Apparatus
Top Guide Inspection Fixture
Pressurizer with a Mechanically Attached Surge Nozzle Thermal Sleeve
Nuclear Reactor Automatic Depressurization System
Anti-Vibration Tube Support Plate Arrangement for Steam Generators
Nuclear Fuel Rod Plenum Spring Assembly
Wireless in-Core Neutron Monitor
Neutron Source Assembly
Noise and Vibration Mitigation System for Nuclear Reactors Employing an Acoustic Side Branch Resonator
Nuclear Reactor Cavity Arrangements for Ice Condenser Plants
Method of Improving Wear and Corrosion Resistance of Rod Control Cluster Assemblies
Chemical Cleaning Method and System with Steam Injection
Control Rod Transfer Device
Minature Sludge Lance Apparatus
Minature Sludge Lance Apparatus
Miniature Sludge Lance Apparatus
Minature Sludge Lance Apparatus
Captive Screw Device and Method
Method and Composition for Removing Deposits
Control Rod Drive Shaft Unlatching Tool
Anti-Vibration Bar Clamping Tool and Method
Fuel Handling Area Passive Filtration Design
Methodology for Modeling the Fuel Rod Power Distribution Within a Nuclear Reactor Core
Zirconium Alloys with Improved Corrosion/Creep Resistance Due to Final Heat Treatments
Nuclear Steam Generator Steam Nozzle Flow Restrictor
Steam Generator Tube Lane Flow Buffer
Submersible Machine Structured to Carry a Tool to a Limited Access Location Within a Nuclear Containment
Tool for Delivery of Testing Element to a Limited Access Location Within a Nuclear Containment
Squib Control Circuit
Rod Position Detection Apparatus and Method
Anti-Clogging Steam Generator Tube Bundle
Method of Achieving Automatic Axial Power Distribution Control
Self-Contained Emergency Spent Nuclear Fuel Pool Cooling System
Semi-Portable Emergency Cooling System for Removing Decay Heat from a Nuclear Reactor
Method of Replacing Shroud of Boiling Water Nuclear Reactor, and Associated Apparatus
Nuclear Fuel Rod Pellet Stack Inspection
Full Spectrum Loca Evaluation Model and Analysis Methodology
Nuclear Reactor Internal Hydraulic Control Rod Drive Mechanism Assembly
Nuclear Reactor Internal Electric Control Rod Drive Mechanism Assembly
Nuclear Control Rod Position Indication System
Retention Apparatus Employing Wedge Element and Engagement Assembly for Use in a Nuclear Application
Support Apparatus for Supporting Dosimetry System in Proximity to Reactor Apparatus
Method of Detecting an Existence of a Loose Part in a Steam Generator of a Nuclear Power Plant
Demister Vane in Situ Cleaning Fixture
Passive Containment Air Cooling for Nuclear Power Plants
Additives for Heat Exchanger Deposit Removal in a Wet Layup Condition
Advanced First Core Fuel Assembly Configuration and Method of Implementing the Same
Underwater Robotic Venting and Inspection System
Instrumentation and Control Penetration Flange for Pressurized Water Reactor
Method of Refueling a Nuclear Reactor
Pressurizer Surge-Line Separator for Integral Pressurized Water Reactors
Inspection Mode Switching Circuit
Nuclear Control Rod with Flexure Joint
Pressurized Water Reactor Compact Steam Generator
Combined Core Makeup Tank and Heat Removal System for a Small Modular Pressurized Water Reactor
Small Modular Reactor Safety Systems
Process for Adding an Organic Compound to Coolant Water in a Pressurized Water Reactor
Dynamic Port for Measuring Reactor Coolant Pump Bearing Oil Level
Axial Flow Steam Generator Feedwater Dispersion Apparatus
Conduit Length Adjustment Apparatus and Method
Pipeline Clamp for Vibration Measurement
Method of Segmenting Irradiated Boiling Water Reactor Control Rod Blades
Method to Extract Tritium from Irradiated Boiling Water Reactor Control Rod Blades
Method to Reduce the Volume of Boiling Water Reactor Fuel Channels for Storage
Apparatus for Vertically Segmenting a Boiling Water Reactor Control Rod Blade
Automated Analysis Coverage Verification (Aacv)
Sliding Duct Connection
In-Core Instrument Thimble Assembly
Deposition of Integrated Protective Material into Zirconium Cladding for Nuclear Reactors by High-Velocity Thermal Application
Optimized Flower Tubes and Optimized Advanced Grid Configurations
Signal Processing of Lamb Wave Data for Pipe Inspection
Heavy Radial Neutron Reflector for Pressurized Water Reactors
Method and Apparatus for the Shielded Relocation of a Nuclear Component
Apparatus and Method for Removing the Upper Internals from a Nuclear Reactor Pressurized Vessel
Method and Apparatus for Refueling a Nuclear Reactor Having an Instrumentation Penetration Flange
Passive System for Cooling the Core of a Nuclear Reactor
Systems and Methods for Generating Power Employing Ves Air Supply Stored Energy
Alternate Passive Spent Fuel Pool Cooling Systems and Methods
Passive Power Production During a Nuclear Station Blackout
Method of Validating Nuclear Reactor in-Vessel Detector Output Signals
Tubesheet Walker for Heat Exchanger Inspections
Tubesheet Gripping Mechanism and Method
Nuclear Fuel Assembly Handling Apparatus
Filter for a Nuclear Reactor Containment Ventilation System
Mobile Boration System
Nuclear Reactor Bottom-Mounted Instrumentation Nozzle Repair Method
Eddy Current Inspection Probe
Apparatus and Method to Inspect, Modify, or Repair Nuclear Reactor Core Shrouds
Pump Seal with Thermal Retracting Actuator
Apparatus and Method to Control Sensor Position in Limited Access Areas Within a Nuclear Reactor
Nuclear Radiation Dosimeter Using Stress Induced Birefringence Changes in Fiber Optic Cables
Application:
13/803,104 →
Publication:
US 2014/0270039
System and Method for Processing Spent Nuclear Fuel
Apparatus and Method to Inspect Nuclear Reactor Components in the Core Annulus, Core Spray and Feedwater Sparger Regions in a Nuclear Reactor
Access Hole Cover Ultrasonic Inspection Tooling
Apparatus to Switch Ultrasonic Signal Paths in a Moderately High Radiation Area
Reactor in-Core Instrument Handling System
Self Powered Neutron Detector
Method and Apparatus for Delivering a Tool to the Interior of a Heat Exchange Tube
Vver-1000 Fuel Assembly Bottom Nozzle
Systems and Methods for Spent Fuel Pool Subcriticality Measurement and Monitoring
Nuclear Fuel Assembly Having a Spacer Grid with One or More Seamless Corners
Systems and Methods for Steam Generator Tube Analysis for Detection of Tube Degradation
Method of Fastening a Captive Screw to a Panel
Captive Screw
Pump Seal with Thermal Retracting Actuator
Ion Chamber Radiation Detector
Sic Matrix Fuel Cladding Tube with Spark Plasma Sintered End Plugs
Jet Pump Diffuser Stack Repair
High Temperature Strength, Corrosion Resistant, Accident Tolerant Nuclear Fuel Assembly Grid
Wireless Transmission of Nuclear Instrumentation Signals
Method for Monitoring Boron Dilution During a Reactor Outage
Steam Generator Dual Head Sludge Lance
Rib-Type Roughness Design for Improved Heat Transfer in Pwr Rod Bundles
Targeted Heat Exchanger Deposit Removal by Combined Dissolution and Mechanical Removal
Ambient Temperature Decontamination of Nuclear Power Plant Component Surfaces Containing Radionuclides in a Metal Oxide
Pump Seal with Thermal Retracting Actuator
Steam Generator Sludge Lance Apparatus
Solid State Electrical Generator
Loop Dissolution System
Patent:
9,718,038 →
Application:
14/195,875 →
Apparatus for Passively Cooling a Nuclear Plant Coolant Reservoir
In-Containment Spent Fuel Storage to Limit Spent Fuel Pool Water Makeup
Reactor Internals Sensor Inserts
Patent:
9,922,737 →
Application:
14/203,679 →
KINETICALLY APPLIED GRADATED Zr-Al-C CERAMIC OR Ti-Al-C CERAMIC OR AMORPHOUS OR SEMI-AMORPHOUS STAINLESS STEEL WITH NUCLEAR GRADE ZIRCONIUM ALLOY METAL STRUCTURE
Double-Sealed Fuel Rod End Plug for Ceramic-Containing Cladding
Ceramic Reinforced Zirconium Alloy Nuclear Fuel Cladding with Intermediate Oxidation Resistant Layer
Low Pressure Drop Nuclear Fuel Assembly Bottom Nozzle
Deposition of a Protective Coating Including Metal-Containing and Chromium-Containing Layers on Zirconium Alloy for Nuclear Power Applications
Control Rod Guide Tube with an Extended Intermediate Guide Assembly
Thermo-Acoustic Nuclear Power Distribution Measurement Assembly
Method and Apparatus for Manipulating Equipment Inside a Steam Generator
Method for In-Core Instrumentation Withdrawal From the Core of a Pressurized Water Reactor
Pressurized Water Reactor Fuel Assembly
Apparatus and Method to Remotely Inspect Piping and Piping Attachment Welds
Electrical System, and Connection Device and Method of Powering a Switchgear Bus in an Electrical System
Deposition of Integrated Protective Material Into Zirconium Cladding for Nuclear Reactors by High-Velocity Thermal Application
Nuclear Fuel Assembly Support Grid
Ultrasonic Phased Array Transducer for the Nde Inspection of the Jet Pump Riser Welds and Welded Attachments
Magneto-Rheological Fluid Based Filter/Reflector
Mobile Boration System
Method for Refueling a Nuclear Reactor Having an Instrumentation Penetration Flange
Nuclear Fuel Assembly Support Feature
A Method of Accessing a Core of a Nuclear Reactor
Zirconium Alloys with Improved Corrosion/Creep Resistance Due to Final Heat Treatments
Zirconium Alloys with Improved Corrosion/Creep Resistance
Under Vessel Automated Work Platform Assembly
Total Integrated Tube Analysis
Chemical Process for Primary System Material Passivation During Hot Functional Testing of Nuclear Power Plants
Method for Measuring Bow/Twist of a Fuel Assembly
Corrosion and Wear Resistant Coating on Zirconium Alloy Cladding
Discharge Apparatus Usable for Determining Neutron Flux
Method of Servicing Modular Plate and Shell Heat Exchanger
Cryogenic System for Spent Nuclear Fuel Pool Emergency Cooling & Safety System
Thermal Retracting Actuator
Passive System for Cooling the Core of a Nuclear Reactor
Modular Electrochemical Machining Apparatus
Application:
14/936,751 →
Publication:
US 2017/0129030
Method for Shielded Relocation of a Nuclear Component
Advanced First Core Fuel Assembly Configuration
Multilayer Composite Fuel Clad System with High Temperature Hermeticity and Accident Tolerance
System Usable in Nuclear Environment for Providing Breathing Gas
Measurement Apparatus for Determining Compressive Loading That Will Be Applied to a Fuel Rod of a Pressurized Water Reactor
Hydraulic Apparatus and Hydraulic Appliance Usable Therein
Method for Delivering a Tool to the Interior of a Heat Exchange Tube
Top Nozzle and Pressurized Water Nuclear Reactor Including Same
Nuclear Control Rod Position Indication System
In-Containment Ex-Core Detector System
Spring Apparatus and Support Apparatus Usable in Nuclear Installation
Method of Detecting and Outputting Radiation Dose Rate Information
Holding Fixture to Assist in Assembly of Support Grid for Nuclear Fuel Rods and Method for Assembling Support Grid for Nuclear Fuel Rods
Remote Heat Removal System
Method of Removing Upper Internals from a Nuclear Reactor Pressurized Vessel
Reactor Coolant System Piping Temperature Distribution Measurement System
Apparatus and Method to Inspect Nuclear Reactor Components in the Core Annulus, Core Spray and Feedwater Sparger Regions in a Nuclear Reactor
Targeted Heat Exchanger Deposit Removal by Combined Dissolution and Mechanical Removal
Deposition of Integrated Protective Material into Zirconium Cladding for Nuclear Reactors by High-Velocity Thermal Application
Nuclear Power Plant Containment Real-Time Remote Operations Management Employing Server and Client
Delivery Device Usable in Laser Peening Operation, and Associated Method
Pulsed Neutron Generated Prompt Gamma Emission Measurement System for Surface Defect Detection and Analysis
Patent:
9,528,952 →
Application:
15/156,757 →
Zirconium-Coated Silicon Carbide Fuel Cladding for Accident Tolerant Fuel Application
Method of Manufacturing a Sic Composite Fuel Cladding with Inner Zr Alloy Liner
Irradiation Target Handling Device for Moving a Target into a Nuclear Reactor
Method of Predicting Wear on Tubes of Steam Generator
Sic Matrix Fuel Cladding Tube with Spark Plasma Sintered End Plugs
Process for Manufacturing Sic Composite Ceramics
Tank Closure Cesium Removal
Alternate Passive Spent Fuel Pool Cooling Systems and Methods
Cold Spray Chromium Coating for Nuclear Fuel Rods
System and Process for Production and Collection of Radioisotopes
Nuclear Instrumentation System High Voltage Power Supply
Patent:
9,998,025 →
Application:
15/341,518 →
Hydrostatic Mechanical Face Seal
Patent:
9,920,839 →
Application:
15/361,755 →
Fuel Assembly with an External Dashpot Disposed Around a Guide Tube Portion
Apparatus for Degassing a Nuclear Reactor Coolant System
In-Core Transmitter Device Structured to Wirelessly Emit Signals Corresponding to Detected Neutron Flux
Recontamination Mitigation Method by Carbon Steel Passivation of Nuclear Systems and Components
Method of Manufacturing a Reinforced Nuclear Fuel Cladding Using an Intermediate Thermal Deposition Layer
Orbital Welder With Integrated Track And Gear Drive
Integration of Real-Time Measurements and Atomistic Modeling to License Nuclear Components
Spacer Grid Using Tubular Cells With Mixing Vanes
Fuel Assembly Arrangement for Retaining Fuel Rod End Plug to Bottom Nozzle
Nuclear Powered Vacuum Microelectronic Device
Thermal Retracting Actuator
Annular Nuclear Fuel Pellets with Central Burnable Absorber
Small Nuclear Reactor Containment System
Vortex Driven Passive Hydrogen Recombiner and Igniter
Method of Detecting and Outputting Radiation Dose Rate Information
Radioisotope Production Target Insert Design and Target Harvesting Methodology for Long Term Irradiation in Commercial Nuclear Reactors
Nuclear Fuel Rod
Modular Plate and Shell Heat Exchanger
Ambient Temperature Decontamination of Nuclear Power Plant Component Surfaces Containing Radionuclides in a Metal Oxide
Detection Apparatus and Method of Detecting the Neutron Absorption Capability of a Control Element of a Nuclear Installation
Inspection Tool
Heat Pipe Molten Salt Fast Reactor with Stagnant Liquid Core
High Temperature Ceramic Nuclear Fuel System for Light Water Reactors and Lead Fast Reactors
Duplex Accident Tolerant Coating for Nuclear Fuel Rods
Apparatus for Planting and Harvesting Radioisotopes on a Mass Production Basis
Base Plate Mounted Core Components for Reliable Rod Assembly and Rapid Field Disassembly
Ultrasonic Phased Array Transducer Apparatus for the Nondestructive Inspection of a Component Under Test
Apparatus for Use in the Inspection of a Top Grid Guide of Boiling Water Reactor
Corrosion and Wear Resistant Coating on Zirconium Alloy Cladding
Method of Predicting Wear on Tubes of Steam Generator
Position-Based Sampling for Eddy Current Inspection of Steam Generator Tubes
Pressure Boundary Bolted Anti-Ejection Device
Reactor Containment Building Spent Fuel Pool Filter Vent
Rotational Apparatus Usable With Control Drum Apparatus In Nuclear Environment
Heat Pipe Assembly of Nuclear Apparatus Having Fiber Optical Temperature Detection System
Method and Apparatus for Inspecting a Fuel Assembly
Steam Generator Sludge Lance Apparatus
Method to Pressurize Sic Fuel Cladding Tube Before End Plug Sealing by Pressurization Pushing Spring Loaded End Plug
Three Dimensional Printed Precision Magnets for Fuel Assembly
COATED U3Si2 PELLETS WITH ENHANCED WATER AND STEAM OXIDATION RESISTANCE
Single Rod Ultrasonic Leak Detection Tool
Nuclear Fuel Assembly Debris Filtering Bottom Nozzle
Steam Generator Dual Head Sludge Lance
Nuclear Reactor System Transmitter Device Structured to Wirelessly Emit a Signal Based on Detected Neutron Flux
Method of Visually Outputting to a Worker During an Operation a Number of Parameters Pertaining to the Operation, and Associated Apparatus
Energy Storage Device
Control Rod Guide Tube with an Extended Intermediate Guide Assembly
Method of Detecting and Outputting Radiation Dose Rate Information
Nuclear Instrumentation Isolated Output Signal Scaling Method and System Employing Same
Method and Apparatus for Enhancing the Electrical Power Output of a Nuclear Reactor Power Generation System
Sequential Embedding Statistical Analysis for Multidimensional Tolerance Limits
Safety System
Method of Locating a Remotely Operated Vehicle Within a Workspace and Remote Inspection System Employing Such Method
Control Rods for Light Water Reactors
Surgically Positioned Neutron Flux Activated High Energy Therapeutic Charged Particle Generation System
Apparatus and Method for Improved Corrosion Thinning Detection
Systems and Methods for Steam Generator Tube Analysis for Detection of Tube Degradation
Combination Reactor Gamma Radiation Power Harvesting Reactor Power Distribution Measurement, and Support to Coolant Freezing Protection System for Liquid Metal and Molten Salt-Cooled Reactor Systems
Pool Type Liquid Metal Fast Spectrum Reactor Using a Printed Circuit Heat Exchanger Connection to the Power Conversion System
Magneto-Rheological Nuclear Reactivity Distribution Control Elements
Electronic Enclosure with Neutron Shield for Nuclear in-Core Applications
Panel Assembly Having Variable Transmissivity and Structural Rigidity
Detection Apparatus Usable In A Nuclear Reactor, and Associated Method
Detection Apparatus Usable In A Nuclear Reactor, and Associated Method
Subcritical Core Reactivity Bias Projection Technique
Method and Apparatus for Real-Time Measurement of Fissile Content Within Chemical and Material Handling Processes
Minimally Invasive Microsampler for Intact Removal of Surface Deposits and Substrates
Dual-Criterion Fuel Canister System
GRAIN BOUNDARY ENHANCED UN AND U3Si2 PELLETS WITH IMPROVED OXIDATION RESISTANCE
Replacing a Thermal Sleeve in a Reactor Vessel Head Adapter
Nuclear Fuel Failure Protection Method
Deposition of Integrated Protective Material into Zirconium Cladding for Nuclear Reactors by High-Velocity Thermal Application
System for the Direct Production of Therapeutic Yttrium-90 for Cancer Treatment
Therapeutic Electron Radiator for Cancer Treatment
System Usable In Nuclear Environment For Providing Breathing Gas
Pin Reforming Tool
Manufacture of Large Grain Powders with Granular Coatings
System and Process for Production and Collection of Radioisotopes
Detection Apparatus and Method of Detecting the Neutron Absorption Capability of a Control Element of a Nuclear Installation
UF6 Transport and Process Container (30W) for Enrichments Up to 20% by Weight
Method and System to Detect and Locate the in-Core Position of Fuel Bundles with Cladding Perforations in Candu-Style Nuclear Reactors
Nuclear Fuel Assembly Support Feature
Dry Cask Storage System Having Detection Apparatus
ELONGATE SiC FUEL ELEMENTS
Silicon Carbide Reinforced Zirconium Based Cladding
Feedwater Sparger Repair
System and Method Enabling Signals from Replacement Self-Powered Neutron Detectors to Be Used to Generate Inputs to Legacy Software
Energy Storage Device
Method of Installing an External Dashpot Tube Around a Control Rod Guide Tube in a Nuclear Fuel Assembly
Detection Apparatus, System, and Method for Detection of Coolant Flow Rate and Temperature in a Nuclear Environment
Fuel Rod Sensor System with Inductive Coupling
Nuclear Control System with Neural Network
Cold Spray Chromium Coating for Nuclear Fuel Rods
In-Containment Spent Fuel Storage to Limit Spent Fuel Pool Water Makeup
Contacting Seal Arrangement for Low and High Pressure Applications
Application:
16/697,351 →
Publication:
US 2021/0156390
Reactor Shutdown System with Melting Gate Member for Segregating Neutron Absorbing Material Compartment from Core
Device and Method for Monitoring a System
Block Style Heat Exchanger for Heat Pipe Reactor
Temperature Measurement Sensor Using Material with a Temperature Dependent Neutron Capture Cross Section
Apparatus and Method to Remotely Inspect Piping and Piping Attachment Welds
Ultrasonic Phased Array Transducer for the Nde Inspection of the Jet Pump Riser Welds and Welded Attachments
Method for Planting and Harvesting Radioisotopes on a Mass Production Basis
Surgically Positioned Neutron Flux Activated High Energy Therapeutic Charged Particle Generation System
Real-Time Reactor Coolant System Boron Concentration Monitor Utilizing an Ultrasonic Spectroscpopy System
Delivery Device Usable in Laser Peening Operation, and Associated Method
Subcritical Reactivity Monitor Utilizing Prompt Self-Powered Incore Detectors
Internal Hydroforming Method for Manufacturing Heat Pipe Wicks
Method of Installing a Heat Pipe Wick into a Container of Differing Thermal Expansion Coefficient
Inspection Tool
Method for Reducing Radiologically-Contaminated Waste
Methods and Systems for Separation of Thorium from Uranium and Their Decay Products
Application:
16/877,156 →
Publication:
US 2021/0354993
Method for Periodically Measuring the Total Gamma Radiation Activity of a Target Radioisotope Being Produced Inside the Core of a Nuclear Reactor
Methods for Manufacturing Nanostructured and Compositionally-Tailored Tubes and Components by Low Temperature, Solid-State Cold Spray Powder Deposition
Method for Installing Extension Tube in a Nuclear Reactor
Wirelessly Emitting Signals Corresponding to Detected Neutron Flux
Articulated Manipulator for Navigating and Servicing a Heat Exchanger
Fuel Assembly Arrangement for Retaining Fuel Rod End Plug to Bottom Nozzle
Irradiation Target Handling Device for Moving a Target into a Nuclear Reactor
Apparatus for Use in the Inspection of a Top Grid Guide of Boiling Water Reactor
Rotational Apparatus Usable with Control Drum Apparatus in Nuclear Environment
Two and Three-Dimensional Model Based Correction of Elbow Tap Flow Measurement
Application:
17/028,297 →
Publication:
US 2022/0090948
Spacer Grid Using Tubular Cells
Replacement Thermal Sleeve for a Reactor Vessel Closure Head Peneration Adapter of Control Rod Drive Mechanism
Coated Fuel Pellets with Enhanced Water and Steam Oxidation Resistance
Detection Apparatus
Detection Apparatus Comprising a Resonant Electrical Circuit Located Within a Nuclear Fuel Rod
Devices, Systems, and Methods for Measuring Radioactive Isotope Production in Bulk
Enhanced Graphite Neutron Reflector with Beryllium Oxide Inclusions
Devices, Systems, and Methods for Adjusting the Output of a Reactor Core
Devices, Systems, and Methods for Configuring the Layout of Unit Cell of a Reactor Core
Application:
17/084,403 →
Publication:
US 2022/0139582
Heat Pipe Having a Wick Between Concentric Inner and Outer Housings, for Use in Heat Removal from a Nuclear Reactor Core
Nuclear Battery
Vortex Driven Passive Hydrogen Recombiner and Igniter
Radioisotope Activity Surveillance Apparatus, System, and Method
NUCLEAR FUEL RODS AND HEAT PIPES IN A GRAPHITE MODERATOR MATRIX FOR A MICRO-REACTOR, WITH THE FUEL RODS HAVING FUEL PELLETS IN A BeO SLEEVE
Systems and Methods for Wireless Remote Control of Automated Equipment
Zirconium-Coated Silicon Carbide Fuel Cladding for Accident Tolerant Fuel Application
Methods of Manufacture for Nuclear Batteries
Autonomous Path Planning and Path Execution for Decontamination of Nuclear Power Plant Objects
Methods for Protection of Nuclear Reactors from Thermal Hydraulic/Neutronic Core Instability
Method of Detecting an Existence of a Loose Part in a Steam Generator of a Nuclear Power Plant
Nuclear Movable Element Position Indication Apparatus, System, and Method
Nuclear Reactor Core Support System Providing Radial and Axial Support
Systems and Methods for Processing Materials with Complex Isotope Vectors for Use as a Nuclear Fuel
Application:
17/165,726 →
Publication:
US 2022/0244200
System for Continually Monitoring the Condition of Nuclear Reactor Internals
Detectors, Systems, and Methods for Continuously Monitoring Neutrons with Enhanced Sensitivity
Repair Process Using Laser Metal Powder Deposition
Application:
17/294,555 →
Publication:
US 2022/0023948
Modular Thermal and Radiation Shielding with Passive Heat Removal
Method and Apparatus for Inspecting a Fuel Assembly
Nuclear Fuel Rod Having Cladding with Varying Diameter
Helium Flow Stop Assembly (Hfsa) for Tig Welding Process of Nuclear Fuel Rods
Method to Pressurize Sic Fuel Cladding Tube Before End Plug Sealing by Pressurization Pushing Spring Loaded End Plug
Application:
17/347,311 →
Publication:
US 2021/0375494
Methods and Devices to Improve Performances of Rcca and Cea to Mitigate Clad Strain in the High Fluence Region
Device For Magnetically Removing A Capsule Containing Co-60 From A Burnable Absorber Rodlet
Method for Installing Extension Tube in a Nuclear Reactor
Fuel Rod Sensor System with Inductive Coupling
Anti-Rotation Arrangement for Thermal Sleeves
Control Rod Drive Mechanism Diagnostic Tool Using Voltage and Current Recordings
Nuclear Fuel Failure Protection System
Pool Type Liquid Metal Fast Spectrum Reactor Using a Printed Circuit Heat Exchanger Connection to the Power Conversion System
System to Detect and Locate the in-Core Position of Fuel Bundles with Cladding Perforations in Candu-Style Nuclear Reactors
Annular Nuclear Fuel Rod
Application:
17/451,726 →
Publication:
US 2023/0132157
Control Rods for Light Water Reactors
Bottom Nozzle with Protective Insert
System and Method for Local Resistivity Measurement and Critical Heat Flux Calculation for Nuclear Reactor Cladding Tubing
Non-Invasive Liquid Metal Flow Measurement in Liquid Metal Fuel Assemblies, Reactor Coolant Pumps, and Test Cartridges
Application:
17/454,920 →
Publication:
US 2023/0154635
GRAIN BOUNDARY ENHANCED UN AND U3Si2 PELLETS WITH IMPROVED OXIDATION RESISTANCE
Fuel Rod Having Heat Transfer Liquid Filling The Gap Between Fuel Pellets And Cladding Tube
Improved Corrosion Resistance of Additively-Manufactured Zirconium Alloys
Application:
17/594,803 →
Publication:
US 2022/0184706
Fuel Assembly Having a Shared Fission Gas Plenum
Application:
17/594,819 →
Publication:
US 2022/0215972
Calibration System and Method
Digital Rod Position Indication System and Method
Passive Venting Arrangement of Stoichiometric Hydrogen Plus Oxygen Gases Generated in a Shielded Container
Bottom Nozzle with Internal Debris Filter
Debris Filtering Skirt Arrangement for Nuclear Fuel Assembly Bottom Nozzle and Bottom Nozzle Including Same
Application:
17/595,499 →
Publication:
US 2022/0215971
System and Method to Determine Reactivity
Application:
17/595,614 →
Publication:
US 2022/0230769
Use of Endothermic Materials in Ice Condenser Containments
Application:
17/597,454 →
Publication:
US 2022/0254525
Injecting Reactant into a Spent Fuel Pool to React with Radioactive Effluent Released into the Pool from a Nuclear Reactor Containment
Nuclear Reactor System, Transmitter Device Therefor, and Associated Method of Measuring a Number of Environmental Conditions
Method and Device for Direct Production of Radio-Isotope Based Cancer Treatment Pharmaceuticals
Surgically Positioned Neutron Flux Activated High Energy Therapeutic Charged Particle Generation System
Device and Method for Rapidly Measuring the Activity of Nuclear Isotopes Contained Within a Cylindrical Enclosure Using the Current Output from a Lead Self-Powered Detector Element
Fuel Cladding Covered by a Mesh
Application:
17/662,692 →
Publication:
US 2023/0368931
Electrochemical Uranium Nitride Production
Physical Vapor Deposition of Ceramic Coatings on Zirconium Alloy Nuclear Fuel Rods
Application:
17/753,744 →
Publication:
US 2022/0375631
Apparatus for Performing in-Situ Adhesion Test of Cold Spray Deposits and Method of Employing
Devices, Systems, and Methods for Detecting Radiation with Schottky Diodes for Enhanced in-Core Measurements
Multiple Nozzle Design in a Cold Spray System and Associated Method
Application:
17/755,030 →
Publication:
US 2022/0389589
Ultrasonic Testing Probe, Couplant Delivery System, and Ultrasonic Testing Apparatus
Ultrasonic Testing Probe, Couplant Delivery System, and Ultrasonic Testing Apparatus
Circuit Breaker Mounting Kit for Use Within a Motor Control Center
Method and Apparatus Employing Vanadium Neutron Detectors
Application:
17/756,955 →
Publication:
US 2022/0415530
Method Of Forming A Unitary Nuclear Fuel Segment By Heat Bonding A Thermally Conductive Layer Deposited On A First Fuel Layer To A Thermally Conductive Layer Deposited On A Second Fuel Layer
Universal Reactor Vessel Head Inspection Platform Assembly
Application:
17/759,415 →
Publication:
US 2023/0343477
Modular Radioisotope Production Capsules and Related Method
Use of Sub-Critical Neutron Multiplication Driven by Electronic Neutron Generators to Produce Radioisotopes
Silicon Carbide Reinforced Zirconium Based Cladding
Devices, Systems, and Methods for Enhancing the Implementation of Control Circuits for Nuclear Instrumentation and Control Systems
Application:
17/813,295 →
Publication:
US 2024/0021333
Method to Reduce Nuclear Radiation Induced Speckling in Video Images
Application:
17/815,470 →
Publication:
US 2024/0037705
Three Dimensional Printed Precision Magnets for Fuel Assembly
Application:
17/815,756 →
Publication:
US 2023/0122593
Three Dimensional Printed Precision Magnets for Fuel Assembly
Application:
17/815,764 →
Publication:
US 2023/0230713
Nuclear Flux Thimble Irradiation Target Insertion and Retrieval Mechanism
Application:
17/823,725 →
Publication:
US 2024/0071642
Cooling Arrangement for Dry Fuel Storage
Method of Replacing a Functionality of a Thermal Shield Flexure, a Thermal Shield Flexure Member, and a System Including the Same
Application:
17/904,132 →
Publication:
US 2023/0136152
Metal Wick Crimping Method for Heat Pipe Internals
High Temperature Hydride Moderator Enabling Compact and Higher Power Density Cores in Nuclear Micro-Reactors
Application:
17/905,704 →
Publication:
US 2023/0107838
Method for Performing Star/Arwv Reconciliation
Application:
17/930,909 →
Publication:
US 2024/0096512
Fiber Reinforced Multi-Layered Wear and Corrosion Coatings of Zirconium Alloy Nuclear Fuel Cladding
Device for Measuring the Activity of Nuclear Isotopes Using a Self-Power Detector
Internal Hydroforming Method for Manufacturing Heat Pipe Wicks Utilizing a Hollow Mandrel and Sheath
A Fixed in-Core Detector Design Using Sic Schottky Diodes Configured with a High Axial and Radial Sensor Density and Enhanced Fission Gamma Measurement Sensitivity
Nuclear Fuel Cladding for Fast Reactors
Channel Boxes for a Boiling Water Reactor and Methods of Manufacture Thereof
Application:
17/997,610 →
Publication:
US 2023/0343475
Compact Passive Decay Heat Removal System for Transportable Micro-Reactor Applications
Application:
17/997,629 →
Publication:
US 2023/0170101
Plated Metallic Substrates and Methods of Manufacture Thereof
Application:
17/997,745 →
Publication:
US 2023/0220556
Self-Powered Nuclear Radiation Detector Comprising a Cable Assembly and a Temperature Compensation Assembly, and Method of Correcting a Temperature Related Change of an Output Signal
Devices, Systems, and Methods for the Enhanced Operation of Hydraulic Control Units of a Control Rod Drive Mechanism to Regulate Nuclear Flux in a Reactor Core
Application:
18/045,562 →
Publication:
US 2024/0120116
Ultrasonic Phased Array Transducer for the Nde Inspection of the Jet Pump Riser Welds and Welded Attachments
Production of Radioisotopes with Highly Enriched Target Enclosure Material
Application:
18/049,343 →
Publication:
US 2024/0136083
Irradiation Target Assembly
Application:
18/049,351 →
Publication:
US 2024/0136082
Heat Pipe Wick Bonding Through Crimping
Patent:
11,858,075 →
Application:
18/049,526 →
Fuel Rod Cladding Comprising A Base Layer, An Interlayer, A Chromium-Containing Primary Layer, And A Top Layer
Application:
18/051,925 →
Publication:
US 2024/0145104
Replacement Thermal Sleeve for a Reactor Vessel Closure Head Penetration Adapter of Control Rod Drive Mechanism
Nuclear Reactor Having Heat Pipes Extend From Core Into A Heat Exchanger
Application:
18/057,208 →
Publication:
US 2024/0170168
Effective Coating Morphology to Protect Zr Alloy Cladding from Oxidation and Hydriding
Application:
18/069,864 →
Publication:
US 2024/0212870
Minimally Invasive Microsampler for Intact Removal of Surface Deposits and Substrates
Devices, Systems, and Methods for Cooling a Nuclear Reactor with Hydride Moderators
Micro-Reactor Core Mechanical Support
Energy Storage System for Nuclear Reactor Remote Installation
Micro-Reactor Fuel Sleeve Assembly
Advanced Manufacturing Heat Pipe Segment with Integral Printed Wick
Automated In-Vessel Neutron Flux Detector System Embedded in Control Drum Assembly
Application:
18/164,964 →
Publication:
US 2024/0266085
Fuel Assembly Arrangement for Retaining Fuel Rod End Plug to Bottom Nozzle
Bellows Pump for Liquid Metals
Inclined Fuel Transfer System Between Containment and Fuel Handling Building
Application:
18/184,324 →
Publication:
US 2024/0312653
Chromium Alloys for Coating Nuclear Fuel Rods
Application:
18/253,982 →
Publication:
US 2024/0093352
High Energy Nuclear Fuel, Fuel Assembly, and Refueling Method
Application:
18/256,397 →
Publication:
US 2024/0047088
Use of Burnable Absorbers in Graphite Matrix of Triso-Fueled Compacts in Nuclear Cores
Application:
18/299,588 →
COATINGS AND SURFACE MODIFICATIONS TO MITIGATE SiC CLADDING DURING OPERATION IN LIGHT WATER REACTORS
Application:
18/305,831 →
Publication:
US 2023/0352199
Temperature Control Device Surrounding Equipment Penetrating a Pressurized Vessel
Application:
18/346,132 →
Publication:
US 2025/0006386
Debris Filtering Arrangement for Nuclear Fuel Assembly Bottom Nozzle and Bottom Nozzle Including Same
Application:
18/359,594 →
Publication:
US 2024/0312646
Internal Hydroforming Method for Manufacturing Heat Pipe Wicks
NUCLEAR FUEL RODS AND HEAT PIPES IN A GRAPHITE MODERATOR MATRIX FOR A MICRO-REACTOR, WITH THE FUEL RODS HAVING FUEL PELLETS IN A BeO SLEEVE
Application:
18/362,734 →
Publication:
US 2024/0312648
Modular Thermal and Radiation Shielding with Passive Heat Removal
Application:
18/397,435 →
Publication:
US 2024/0170169
Core Component Rodlet for Irradiating Isotope Targets in Pressurized Water Reactor Conditions
Application:
18/403,870 →
Publication:
US 2025/0226122
Core Component Rodlet with Reattachment Capability
Application:
18/403,897 →
Publication:
US 2025/0226126
Multi-Material Printed Heat Exchanger Produced by Diffusion Bonding
Application:
18/467,395 →
Publication:
US 2025/0093113
Neutron Radiation Detector
Application:
18/467,462 →
Publication:
US 2025/0093537
Detection Apparatus Comprising a Resonant Electrical Circuit Located Within a Nuclear Fuel Rod
Devices, Systems, and Methods for Detecting Radiation with Schottky Diodes for Enhanced In-Core Measurements n-Core Measurements
Method of Magnetically Removing an Irradiated Capsule from a Burnable Absorber Rodlet
Shaft Coupling and Uncoupling Tool
Application:
18/485,548 →
Publication:
US 2025/0125062
Method for Continually Monitoring the Condition of Nuclear Reactor Internals
Application:
18/487,360 →
Publication:
US 2024/0112824
Expandable Plug and Pressure Tool for Use in Metallic Wick Pore Size Testing
Application:
18/499,904 →
Publication:
US 2025/0137903
Gadolinium Oxide Nano Particles in Coolant for Reactivity Control
Application:
18/503,915 →
Publication:
US 2025/0149193
Recovery of Uranium Metal Using Eutectic Compositions
Application:
18/509,127 →
Publication:
US 2025/0154628
Devices, Systems, and Methods for Power Generation Using Irradiators and Other Gamma Ray Sources
Application:
18/547,936 →
Publication:
US 2024/0153664
Devices, Systems, and Methods for Delivering Delta Radiation Using Prompt Neutron Capture Gamma Radiation
Application:
18/547,952 →
Publication:
US 2024/0136085
Core Barrel Plug
Application:
63/599,505 →
Related Assignments
(25)
Other recorded transfers of the patents in this record — the chain of ownership.
Security Interest
Aug 1, 2018
From: WESTINGHOUSE ELECTRIC COMPANY LLC; FAUSKE AND ASSOCIATES LLC
To: CREDIT SUISSE AG, CAYMAN ISLANDS BRANCH, AS COLLATERAL AGENT
Reel/Frame 046708/0222 →
Security Interest
Aug 1, 2018
From: WESTINGHOUSE ELECTRIC COMPANY LLC; FAUSKE AND ASSOCIATES LLC
To: BANK OF MONTREAL, AS ADMINISTRATIVE AGENT
Reel/Frame 046708/0639 →
Security Interest
Aug 1, 2018
From: WESTINGHOUSE ELECTRIC COMPANY LLC; FAUSKE AND ASSOCIATES LLC
To: GOLDMAN SACHS BANK USA, AS COLLATERAL AGENT
Reel/Frame 046708/0332 →
Release of Security Interest in Patents
Aug 1, 2019
From: GOLDMAN SACHS BANK USA, AS COLLATERAL AGENT
To: WESTINGHOUSE ELECTRIC COMPANY LLC; FAUSKE AND ASSOCIATES LLC
Reel/Frame 049937/0032 →
Patent Security Agreement
May 27, 2022
From: WESTINGHOUSE ELECTRIC COMPANY LLC; BHI ENERGY I SPECIALTY SERVICES LLC
To: BANK OF MONTREAL, AS COLLATERAL AGENT
Reel/Frame 060791/0372 →
Assignment of Assignor's Interest
Oct 21, 2022
From: OLSON, LUKE C.; METZGER, KATHRYN E.; LAHODA, EDWARD J.; ROBERTS, ELWYN
To: WESTINGHOUSE ELECTRIC COMPANY LLC
Reel/Frame 061493/0508 →
Assignment of Assignor's Interest
Nov 8, 2022
From: ALESHIN, YURIY; DO, THANH H.
To: WESTINGHOUSE ELECTRIC COMPANY LLC
Reel/Frame 061692/0885 →
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Nov 14, 2022
From: ARNDT, JEFFREY L.; FERRONI, PAOLO; STANSBURY, CORY A.
To: WESTINGHOUSE ELECTRIC COMPANY LLC
Reel/Frame 061761/0401 →
Assignment of Assignor's Interest
Jan 26, 2023
From: CONGEDO, THOMAS V.
To: UNIVERSITY OF PITTSBURGH - OF THE COMMONWEALTH SYSTEM OF HIGHER EDUCATION
Reel/Frame 062500/0929 →
Assignment of Assignor's Interest
Jan 26, 2023
From: HEIBEL, MICHAEL D.
To: WESTINGHOUSE ELECTRIC COMPANY LLC
Reel/Frame 062500/0501 →
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Jan 26, 2023
From: LOPRESTI, BRIAN J.
To: UNIVERSITY OF PITTSBURGH - OF THE COMMONWEALTH SYSTEM OF HIGHER EDUCATION
Reel/Frame 062500/0651 →
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To: WESTINGHOUSE ELECTRIC COMPANY LLC
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Mar 15, 2023
From: TAYLOR, CREED; BURR, JASON D.
To: WESTINGHOUSE ELECTRIC COMPANY LLC
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Apr 21, 2023
From: GARING, JOHN, III; HEIBEL, MICHAEL D.; PRIBLE, MICHAEL C.
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Assignment of Assignor's Interest
May 10, 2023
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To: WESTINGHOUSE ELECTRIC COMPANY LLC
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Jun 15, 2023
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To: WESTINGHOUSE ELECTRIC COMPANY LLC
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Jul 18, 2023
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To: WESTINGHOUSE ELECTRIC COMPANY LLC
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Jul 18, 2023
From: TWEEDLE, THOMAS; BOBKO, PAUL A.
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Aug 31, 2023
From: HEIBEL, MICHAEL D.
To: WESTINGHOUSE ELECTRIC COMPANY LLC
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Aug 31, 2023
From: PETROSKY, LYMAN J.
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Assignment of Assignor's Interest
Oct 11, 2023
From: MEIER, CHRISTOPHER P.; LAUBHAM, ADAM M.
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Assignment of Assignor's Interest
Oct 20, 2023
From: LOJEK, JOHN, III; LAPRESTI, MICHAEL; BLUNT, RORY A.F.; NESTOR, CHRISTOPHER M.
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